Published December 2005 | Version v1
Journal article

Partial service life assessment of a reactor containment

  • 1. Czech Technical University in Prague, Faculty of Civil Engineering, Thakurova 7, 166 29 Prague (Czech Republic)

Description

A service life assessment of a prestressed concrete containment is developed. Liner strain is the sole limit state criterion considered, the LOCA accidents represent the load effects and the creep induced loss of prestress affects the time dependent structure resistance. Poisson, Gaussian and Ferry Borges-Castanheta processes are adopted for load models and their predictions are compared on the background of a specific PWR installation. Available experimental data is used to optimize the theoretical creep law. The Poisson and FBC processes show negligible difference for actual pulse intensities and the required service life

Additional details

Identifiers

DOI
10.1016/j.nucengdes.2005.06.010;
PII
S0029-5493(05)00236-0;

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
235
Journal Issue
23
Journal Page Range
p. 2451-2462
ISSN
0029-5493
CODEN
NEDEAU

Optional Information

Copyright
Copyright (c) 2005 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.